Feed Materials Production Center Summary Technical Report: July 1, 1963-September 30, 1963 (open access)

Feed Materials Production Center Summary Technical Report: July 1, 1963-September 30, 1963

From abstract: The temperature of molten uranium was measured indirectly by an infrared radiation pyrometer. The emissivities of graphite and molten uranium were determined, and a series of equations correlating pyrometer readings with melt temperatures was derived.
Date: October 28, 1963
Creator: unknown
System: The UNT Digital Library
A Photographic Study of Boiling Flow (open access)

A Photographic Study of Boiling Flow

From abstract: A high speed motion picture study was conducted of boiling flow in a vertical, rectangular channel at atmospheric pressure. Three different visual flow regimes were defined and described.
Date: October 25, 1963
Creator: Vohr, John Henry
System: The UNT Digital Library
Specifications and Procedures Used in Manufacturing U₃O₈-Aluminum Dispersion Fuel Elements for Core I of the Puerto Rico Research Reactor (open access)

Specifications and Procedures Used in Manufacturing U₃O₈-Aluminum Dispersion Fuel Elements for Core I of the Puerto Rico Research Reactor

Report containing the description and design of U₃O₈-Aluminum Dispersion Fuel Elements for Core I of the Puerto Rico Research Reactor. Topics include the requirements of core materials, materials specifications, manufacturing procedures, and shipping preparation.
Date: October 21, 1963
Creator: Kucera, W. J.; Leitten, C. F., Jr. & Beaver, R. J.
System: The UNT Digital Library
Development and Demonstration of an Ion-Exchange Process for Kilogram-Scale Production of High Purity Promethium (open access)

Development and Demonstration of an Ion-Exchange Process for Kilogram-Scale Production of High Purity Promethium

Report regarding "the development of a process suitable for large-scale separation of highly purified promethium from the trivalent fission product rare earth mixture" (p. 3).
Date: October 1963
Creator: Wheelwright, E. J. (Earl J.) & Roberts, F. P.
System: The UNT Digital Library
Final Summary Report of the Gas-Cooled Reactor Experiment-1 (open access)

Final Summary Report of the Gas-Cooled Reactor Experiment-1

Report describing the Gas-Cooled Reactor test facility, its ongoing testing and evaluations of a test reactor, and its operating conditions and characteristics.
Date: October 1963
Creator: Chesworth, R. H.
System: The UNT Digital Library
Fundamentals in the Operation of Nuclear Test Reactors: Volume 2, Materials Testing Reactor Design and Operation (open access)

Fundamentals in the Operation of Nuclear Test Reactors: Volume 2, Materials Testing Reactor Design and Operation

Second volume of reports on the operation of nuclear test reactors. It includes six chapters: engineering description fo the materials testing reactor, reactor control components and instrumentation, reactor control circuitry, reactor operation, reactor shutdown and tank work, and supplemental facilities at the materials testing reactor.
Date: October 1963
Creator: Phillips Petroleum Company
System: The UNT Digital Library
Health and Safety Laboratory Fallout Program Quarterly Summary Report: June 1, 1963 - September 1, 1963 (open access)

Health and Safety Laboratory Fallout Program Quarterly Summary Report: June 1, 1963 - September 1, 1963

Report that summarizes multiple laboratories' reports on global fallout deposition. Reports include data on Strontium-90 deposition recorded by the Health and Safety Laboratory, data from other laboratories, related interpretive reports, and recent publications related to fallout.
Date: October 1, 1963
Creator: Hardy, Edward P., Jr.; Rivera, Joseph & Collins, William R., Jr.
System: The UNT Digital Library
A Method for Beta-Gamma Hand and Shoe Counting Under Varying Background Conditions (open access)

A Method for Beta-Gamma Hand and Shoe Counting Under Varying Background Conditions

Report containing a method for beta-gamma counting of hands, shoes, and clothing via an instrument that employs scintillation detectors and solid-state circuits.
Date: October 1963
Creator: Spear, W. G.
System: The UNT Digital Library
Specifications for Swage Compacted, Mixed Oxide (UO2-PuO2), Fuel Elements for the Plutonium Recycle Test Reactor (MARK I-M) (open access)

Specifications for Swage Compacted, Mixed Oxide (UO2-PuO2), Fuel Elements for the Plutonium Recycle Test Reactor (MARK I-M)

Report containing the dimensions, materials, and fabrication details for swage compacted, mixed oxide (UO2-PuO2), fuel elements for the Plutonium Recycle Test Reactor (MARK I-M).
Date: October 1963
Creator: Hanford Atomic Products Operation
System: The UNT Digital Library
Specifications for Vibrationally Compacted, Mixed Oxide (UO2-PuO2), Fuel Elements for the Plutonium Recycle Test Reactor (MARK I-L) (open access)

Specifications for Vibrationally Compacted, Mixed Oxide (UO2-PuO2), Fuel Elements for the Plutonium Recycle Test Reactor (MARK I-L)

Report describing the dimensions, materials, and fabrication of vibrationally compacted, mixed oxide (UO2-PuO2) fuel elements for the Plutonium Recycle Test Reactor (MARK I-L). Appendix begins on page 38.
Date: October 1, 1963
Creator: Hanford Atomic Products Operation
System: The UNT Digital Library